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Citation(s) in
RCA
7
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For:
Zimmermann H
.
Fission Gas Behavior in Oxide Fuel Elements of Fast Breeder Reactors.
NUCL TECHNOL
2017. [DOI:
10.13182/nt76-a31546
]
[
Citation(s) in
RCA
: 11
]
[
Impact Index Per Article: 1.6
]
[
Reference Citation Analysis
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[Indexed: 11/12/2022]
Number
Cited by Other Article(s)
1
Modeling of Equiaxed Grain Growth in Uranium Dioxide Fuels.
NUCL TECHNOL
2017. [DOI:
10.13182/nt79-a32326
]
[
Citation(s) in
RCA
: 2
]
[
Impact Index Per Article: 0.3
]
[
Reference Citation Analysis
]
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[Indexed: 11/12/2022]
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2
ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements.
NUCL TECHNOL
2017. [DOI:
10.13182/nt79-a32279
]
[
Citation(s) in
RCA
: 33
]
[
Impact Index Per Article: 4.7
]
[
Reference Citation Analysis
]
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[Indexed: 11/12/2022]
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3
Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor.
ATOM ENERGY+
2017. [DOI:
10.1007/s10512-017-0221-4
]
[
Citation(s) in
RCA
: 1
]
[
Impact Index Per Article: 0.1
]
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[Indexed: 10/19/2022]
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4
Distribution characteristics of fission gas along the axial direction for an irradiated fuel rod of a pressurized water reactor (PWR).
J Radioanal Nucl Chem
2013. [DOI:
10.1007/s10967-013-2574-z
]
[
Citation(s) in
RCA
: 3
]
[
Impact Index Per Article: 0.3
]
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[Indexed: 10/26/2022]
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5
Gas phase in experimental fuel elements with compact uranium dioxide, irradiated in the SM-2 reactor.
ATOM ENERGY+
1984. [DOI:
10.1007/bf01123751
]
[
Citation(s) in
RCA
: 0
]
[
Impact Index Per Article: 0
]
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[Indexed: 10/25/2022]
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6
Gas Tag Identification of Failed Reactor Assemblies—IV. Analysis Methods.
NUCL TECHNOL
1980. [DOI:
10.13182/nt80-3
]
[
Citation(s) in
RCA
: 5
]
[
Impact Index Per Article: 0.1
]
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[Indexed: 11/12/2022]
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7
Prediction of Fission Gas Retained in Mixed-Oxide Fuels.
NUCL TECHNOL
1977. [DOI:
10.13182/nt77-a39706
]
[
Citation(s) in
RCA
: 0
]
[
Impact Index Per Article: 0
]
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[Indexed: 11/12/2022]
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